ML18041A197

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Amend 111 to License DPR-72,clarifying Portion of Section 6, Administrative Control, & Modifies Audit Frequencies of Security,Emergency & Fire Protection Plans Per 10CFR73.40(d)
ML18041A197
Person / Time
Site: Crystal River 
(DPR-72-A-111)
Issue date: 05/05/1989
From: Berkow H
Office of Nuclear Reactor Regulation
To:
Shared Package
ML18041A198 List:
References
NUDOCS 8905180243
Download: ML18041A197 (58)
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Text

Nine Mile Point Unit 2.FSAR CHAPTER 3 TABIE OF CONTENTS (Cont)

Section Title Pacae 3.4. 1. 1.4 3.4.1.1.5 3.4.1.2 3.4.2 3.4.3 Procedures Required for Cold Shutdown of Reactor in Flood Identity of Safety-Related Systems or Components Capable of Functioning in Flooded or Partially Flooded Conditions Permanent Dewatering System Analytic and Test Procedures References

3. 4-3 3.4-3 3.4-3 3.4-4 3.4-6 3.5 3.5.1 3.5.1.1 3.5.1.1.1 3.5.1.1 '

3.5.1.1.3 3.5.1.1.4 3.5.1.1.5 3.5.1.2 3.5.1.3 3'.5.1.3.1 3.5.1.3.2 3.5.1.3.3 3.5.1.3.4 3.5.1.3.5 3.5.1.3.6 3.5.1.4 3.'5.1.5 3.5.1.6 3.5.2 3.5.3 3.5.4 MISSILE PROTECTION Missile Selection and Description Internally Generated Missiles Locations of Structures,

Systems, and Components Applicable Seismic Category and Quality Group Classifications Piping and Instrumentation Drawings Identification of Missiles, Their
Sources, and Basis of Selection Missile Protection Provided Internally Generated Missiles (Inside Containment)

Turbine Missiles Turbine Placement and Orientation Missile Identification, Characteristics, and Target Description Probability Analysis Turbine Overspeed Protection Turbine Valve Testing Turbine Characteristics Missiles Generated by Natural Phenomena Missiles Generated by Events Near the Site Aircraft Hazards Structures,

Systems, and Components to be Protected from Externally Generated Missiles Barrier Design'rocedures References 3.5-1 3.5-1 3.5-3 3.5-3 3.5-3 3.5-3 3.5-3 3 '

4b I

as 3.5-6 3.5-6 3.5-6 3.5-7 3.5-8 3.5-15 3.5-18 3.5-18 3.5-18 3.5-18 3.5-18 3.5-18 3.5-19 3.5-22 Amendment 25 3-v March 1986

Nine Mile Point Un'it 2

FSAR CHAPTER 3

TABLE OF CONTENTS (Cont)

Section 3.6 3.6A 3.6.1A 3.6.1.1A 3.6.1.2A 3.6.1.3A 3.6.1.3.1A 3.6.1.3.2A 3.6.1.3 'A 3.6.2A 3.6.2.1A

3. 6:2. l. 1A 3.6.2.1.2A 3.6.2.2A 3.6.2 3.6.2 3.6.2 3.6.2 3 ' '

3.6 '

3.6.2

.2.1A

2.2A

~ 2.3A

.2.4A

.2.5A

.2.6A

.2.7A 3.6.2.1.3A 3.6.2 '

~ 4A I

3.6.2.1.5A 3.6.2.1.6A Title PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING PROTECTION AGAINST EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING (SWEC SCOPE OF SUPPLY)

Postulated Piping Failures in Fluid Systems Inside and Outside the Containment Design Bases Description of Piping Failures Safety Evaluation Approach Protection Methods Specific Protection Measures Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping Criteria Used to Define Break and Crack Location and Configuration Definition of High-Energy Fluid System Definition of Moderate-Energy Fluid System Postulated Pipe Breaks and Cracks Exemptions From Pipe Whip Protection Requirements Postulated Pipe Break Locations Design Basis Break/Crack Types and Orientation Analytical Methods to Define Forcing Functions and Response Models Introduction Time-Dependent Blowdown Force Simplified Blowdown Analysis Lumped-Parameter Dynamic An'alysis Energy Balance" Analysis Local Pipe Indentation Concrete Barrier Impact Pacae 3.6A-1 3.6A-2 3.6A-2 3.6A-2 3.6A-5 3.6A-6 3.6A-6 3.6A-6'.6A-8 3.6A-9 3.6A-9 3.6A-9 3.6A-9 3.6A-10 3.6A-10a 3.6A-11 3.6A-18

'3.6A-21 3.6A-21 3.6A-22 3.6A-28 3.6A-28a 3.6A-30 3.6A-32 3.6A-33 USAR Revision April 1989

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section 3.6.2.3A 3.6.2.3.1A 3.6.2.3.2A 3.6.2.4A 3.6.2.5A 3.6.3A 3.6B 3.6.1B 3.6.2B 3.6.2.1B O

3.6.2.1.1B 3.6.2.1.1.1B 3.6.2.1.1.2B 3.6.2.1.1.3B 3.6.2.1.1.4B 3.6.2.1.1.5B 3.6.2.1.1.6B 3.6.2.1.1.7B 3.6.2.1.1.8B 3.6.2.1.2B 3.6.2.2B 3.6.2.2.1B 3.6.2.2.1.1B Title Dynamic Analysis Methods to Verify Integrity and Operability Jet Impingement Analysis Pipe Rupture Restraints Guard Pipe Assembly Design Criteria Material for the Operating License Review References PROTECTION AGAINST DYNAMIC EFFECTS ASSOCIATED WITH POSTULATED RUPTURE OF PIPING (GE SCOPE OF SUPPLY)

Postulated Piping Failures in Fluid Systems Outside of Containment Determination of Break Locations and Dynamic Effects Associated with the Postulated Rupture of Piping Criteria Used to Define Break and Crack Location and Configuration Criteria for Recirculation Piping System Inside Containment Definition of High Energy Fluid System Definition of Moderate Energy Fluid System Postulated Pipe Breaks and Cracks Exemptions from Pipe Whip Protection Requirements Location for Postulated Pipe Breaks (ASME Safety Class 1 Piping)

Other High Energy Piping and Moderate Energy Piping Regulatory Guide 1.46 Types of Breaks to Be Postulated in Fluid System Piping Criteria for Piping System in Area of Containment Isolation Valves Analytical Methods to.Define Blowdown Forcing Functions and

Response

Models Analytical Methods to Define Blowdown Forcing Functions Recirculation Piping System Pacee

3. 6A-34 3.6A-34 3.6A-35 3.6A-37 3.6A-37 3.6A-38
3. 6B-1
3. 6B-1 3.6B-1 3.6B-1 3.6B-1 3.6B-1 3.6B-2 3.6B-2
3. 6B-3 3.6B-4 3.6B-5 3.6B-5 3.6B-5 3.6B-7 3.6B-7
3. 6B-7
3. 6B-7 USAR Revision 3 vii October 1991

.Nine Mile Point Unit 2 FSAR CHAPTER 3

TABLE OF CONTENTS (Cont)

Section 3.6.2.2.2B 3.6.2.2.2.1B 3,.6.2.3B 3.6.2.3.1B 3.6.2 '.2B 3.6.2.3.2.1B 3.6.2.3.3B 3.6.2.3.3.1B 3.6.2.4B 3 '.2.4.1B

3. 6. 2. 4. 2B 3.6.2.4.3B 3.6.3B 3.7 3.7A 3.7.1A 3.7.1.1A 3.7.1.2A 3.7.1.3A 3.7.1.3.1A 3.7.1.3.2A 3.7.1.3.3A 3.7.1

~ 4A

3. 7.2A 3.7..2.1A 3.7.2.2A Title Pipe Whip Dynamic Response Analyses Recirculation Piping System Dynamic Analysis Methods to Verify Integrity and Operability Jet Impingement Analyses and Effects on Safety-Related Components Pipe Whip Effects on Safety-Related Components Pipe Whip Effects Following a Postulated Rupture of the Recirculation Piping System Loading Combinations and Design Criteria for Pipe Whip Restraints Recirculation Piping System Pipe Whip Restraints Material to Be Submitted for the Operating License Review Implementation of Criteria for Pipe Break and Crack Location and Orientation Implementation of Speci al Protection Criteria Summary of Jet, Effects Analyses Results References SEISMIC DESIGN SEISMIC DESIGN (SWEC SCOPE OF SUPPLY)

Seismic Input Design Response Spectra Design Response Spectra Derivation Critical Damping Values Structures Equipment Piping Supporting Media for Category I Structures Seismic System Analysis Seismic Analysis Methods Natural Frequencies and Response Loads Parcae 3.6B-10 3.6B-10 3.6B-12 3.6B-12

3. 6B-13
3. 6B-13
3. 6B-13 3.6B-14 3.6B-19 3.6B-19 3.6B-20
3. 6B-20 3.6B-21 3.7A-1 3.7A-1 3.7A-1 3.7A-1 3.7A-1 3.7A-2 3.7A-2 3.7A-3 3.7A-3 3.7A-3 3.7A-3, 3.7A-3 3.7A-S

Nine Mile Point Unit 2 FSAR CHAPTER 3

TABLE OF CONTENTS (Cont)

Section 3'7 ~ 2 ~ 3A 3.7 '.4A 3.7 ' '.1A 3.7.2.5A 3.7 '.6A 3e7

~ 2'A 32 'A 3.7 ';9A 3.7. 2.10A 3.7.2.11A 3.7.2.12A 3.7.2.13A 3 ' '.14A 3.7.2.15A 3 ' 'A 3.7.3 'A 3.7

~ 3 ~ 1.1A 3.7 '.1 ~ 2A 3.7 '.1.3A 3'.3 'A 3 ' ' 'A 3.7 ~ 3 ~ 3 ~ 1A 3 ' '.3.2A 3 ' ' '.3A 3.7 '.3.4A 3.7 '.3 'A 3.7 '.4A 3.7.3.4.1A 3.7 ' ' 'A 3'.3 'A 3 '

3.6A 3.7.3 'A Title Procedure Used for Modeling Soil/Structure Interaction Rock/Structure Interaction Development of Floor Response Spectra Three Components of Earthquake Motion Combination of Modal Responses Interaction of Non-Category I Structu'res With Category I Structures Effects of Parameter Variations on Floor Response Spectra Use of, Constant Vertical Static Factors Method Used to Account for Torsional Effects Comparison of Responses Methods for Seismic Analysis of Dams Determination of Category I Structure Overturning Moments Analysis Procedure for Damping Seismic Subsystem Analysis Seismic Analysis Methods Seismic Qualification of. Components Seismic Analysis of Piping Systems Other Dynamic Loads Determination of Number of

'quivalent Stress Cycles Procedure Used for Modeling Summary Geometric Boundaries of Analytical Models Model Selection of Mass Points Number of Modes and Cutoff Frequency Basis for Selection of Frequencies Components Piping Use of Equivalent Static Load Method of Analysis Three Components of Earthquake Motion Combination of Modal Responses

,Pacae 3.7A-5a 3.7A-6 3.7A-7 3 'A-7 3 'A-9 3.7A-9 3.7A-10 3.7A-10 3.7A-ll 3.7A-11 3.7A-11

3. 7A-ll
3. 7A-12 3.7A-12 3.7A-13 3 'A-13 3.7A-13 3 'A-18 3.7A-19
3. 7A-19 3.7A-19 3.7A-19 3 'A-19 3.7A-20 3 'A-20 3.7A-20a 3.7A-21 3.7A-21 3 'A-22 3.7A-22 3 7A-22a 3.7A-22a USAR Revision 0

April 1989

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section 3.7.3.8A 3.7.3.8.1A 3.7.3.8;2A 3.7.3.8.3A 3.7.3.9A 3.7.3.10A 3.7.3.11A 3.7.3.12A 3.7;3.13A 3.7.3.14A 3.7.3.15A 3.7.4A 3.7.4.1A 3.7.4.2A 3.7.4.2.1A

3. 7. 4. 2. 2A, 3.7.4.2.3A 3.7.4.2.4A 3.7.4.3A 3.'7.4.4A 3.7.4.5A 3.7.5A 3.7B 3.7.1B 3.7.1.1B 3.7.1.2B 3.7.1.3B 3.7.1.4B 3.7.2B 3.7.2.1B 3.7.2.1.1B

'Title Analytical Procedures for Piping Introduction Analytical Techniques Dynamic Analysis Multiply Supported Equipment Components with Distinct Inputs Use of Constant Vertical Static Factors Torsional Effects of Eccentric Masses Buried Category I Piping Systems and Tunnels Interaction of Other Piping with Category I Piping Seismic Analyses for Reactor Internals Analysis Procedure for Damping Criteria for Seismic Instrumentation Program Comparison with Regulatory Guide 1.12 Location and Description of Instrumentation Triaxial Time History Accelerograph Triaxial Peak Acce'lerograph Triaxial Response Spectrum Recorder Triaxial Seismic Switch Main Control Room Operator Notification Comparison of Measured and Predicted Responses Inservice Surveillance Requirements References SEISMIC DESIGN (GE SCOPE OF SUPPLY)

Seismic Input Design Response Spectra Design Time History Critical Damping Values Supporting Media for Category I Structures Seismic System Analysis Seismic Analysis Methods The Equations of Dynamic Equilibrium Pacae

3. 7A-23
3. 7A-23 3.7A-23 3.7A-24 3.7A-27a 3.7A-28 3.7A-28 3.7A-28 3.7A-28a 3.7A-28a 3.7A-29 3.7A-29 3.7A-29 3.7A-29 3.7A-29 3.7A-30 3.7A-31 3.7A-31 3.7A-32 3.7A-33 3.7A-33 3.7A-34 3.7B-1 3.7B-1 3.7B-1 3.7B-2 3.7B-2 3.7B-2 3.7B-2 3.7B-2 3.7B-3 USAR Revision 4

3 x October 1992

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section 3.8.1.4.2 3.8.1.5 3.8.1.5.1-3.8.1.5.2 3.8.1.6 3.8.1.6.1 3.8.1'.6.2 3.8.1,.6.3 3.8.1.7 3.8.1.7.1 3.8.1.7.2 3.8.2 3.8.3 3.8.3.1 3.8.3.1.1 3.8.3.1.2 3.8.3.1.3 3.8.3.1.4 3.8.3.1.5 3.8.3.2

3. 8. 3.2. 1 3.8.3.2.2 3.8.3.3 3.8.3.3.1 3.8.3.3.2 3.8.3.3.3 3.8.3.4 3.8.3.4.1 3.8.3.4.2 3.8.3.4.3 3.8.3.4.4 3.8.3.4.5 3.8.3.5

.Title Steel Liner and Penetrations Structural Acceptance Criteria Primary Containment Structure Steel Liner and Penetrations Materials, Quality Control, and Construction Techniques Concrete Primary Containment Structure Steel Liner and Penetrations Exceptions and/or Clarifications to ASME Code Testing and Inservice Inspection Concrete Containment Steel Liner and Penetrations Not Applicable Concrete and Steel Internal Structures of the Primary Containment Description of the Internal Structures Drywell Floor Reactor Vessel Pedestal Biological Shield Wall Star Truss Floors Applicable Codes, Standards, and Specifications Biological Shield.Wall Star Truss Loads and Loading Combinations Drywell Floor and Reactor Vessel Pedestal Biological Shield Wall Star Truss Design and Analysis Procedures Drywell Floor Reactor Pedestal Biological Shield Wall Star Truss Floors Structural Acceptance Criteria Pacae 3.8-13 3.. 8-16 3.8-16 3.8-16 3.8-17 3.8-17 3.8-17 3.8-24 3.8-26 3.8-26 3.8-26a 3.8-27 3.8-27 3.8-27 3.8-28 3.8-29 3.8-30 3.8-30 3.8-30 3.8-31 3.8-31

3. 8-"32 3.8-32 3.8-32 3.8-32 3.8-33 3.8-33 3.8-33 3.8-34 3.8-35 3.8-36 3.8-36 3.8-37 USAR Res'ision 4

3 xiii October 1992

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE. OF CONTENTS (Cont)

Section 3.8.3.6 3.8.3.6.1 3.8.3.6.2 3.8.3.6.3 3.8.3.7 3.8.4 3.8.4.1 3.8.4.1.1 3.8.4.1.2 3.8.4.1.3 3.8.4.1.4 3.8.4.1.5 3.8.4.1.6 3.8.4.1.7'.8.4.1.8 3.8.4.1.9 3.8.4.1.10 3.8.4.1.11 3.8.4.1.12 3.8.4.2.

3.8.4.3 3.8.4.4 3.8.4.4.1 3.8.4.4.2 3.8.4.4.3 3.8.4.4.4 3.8.4.4.5 3.8..4.4.6 3.8.4.4.7 3.8.4.4.8 3.8.4.4.9 3.8.4.4.10 3.8.4.4.11 3.8.4.4.12 Title Materials, Quality Control, and Special Construction Techniques Reactor Uessel Pedestal and Drywell Floor Biological Shield Wall Star Truss Testing'nd Inservice Surveillance Requirements Other Seismic Category I Structures Description of the Structures Reactor Building Control Room Building Diesel Generator Building Screenwell Building Intake Structures Intake (and Discharge)

Tunnels Electrical Tunnels and Piping Tunnels Main Stack Standby Gas Treatment Building and Railroad Access Lock Area Auxiliary Service Building Radwaste Building Turbine Building Applicable Codes, Standards, and Specifications Ioads and Load Combinations Design and Analysis Procedures Reactor Building Control Room Building Diesel Generator Building Screenwell Building Intake Structures Intake (and Discharge)

Tunnels Electrical Tunnels and Piping Tunnels Main Stack Standby Gas Treatment Building and Railroad Access Lock Area Auxiliary Service Building Radwaste Building Turbine Building Pacae

3. 8-38 3.8-38 3.8-38 3.8 3.8-39 3.8-39 3.8-39 3.8-41 3.8-43 3.8-43 3.8-44 3.8-44 3.8-45 3.8-45 3.8-45a 3.8-46 3.8-46 3.8-47 3.8-47 3.8-49 3.8-5la 3.8-52 3.8-53 3.8-56 3.8-56 3.8-57 3.8-57 3.8>>57 3.8-58 3.8-58 3.8-58 3.8-58 3.8-58 3.8-59 Amendment 8

3 xiv January 1984

Nine Mile Point Unit.2 FSAR Section 3.8.4.5 3.8.4.6 3.8.4.6.1 3.8.4.6.2 3.8.4.6.3 3.8.4.7 3.8.5 3.8.5.1 3.8.5.1.1 3.8.5.1.2 3.8.5.2 3.8.5.3

'3.8.5.4 3.8.5.5

'.'8.5 '

3.8.5 '

3.8.6 3.9 3.9A 3.9.1A 3.9.1

~ lA 3.9.1.2A 3.9 '

~ 3A 3.9.1.4A 3.9.1.4.1A 3.9.1.4.1.1A 3.9.1.4.2A 3.9.1.5A 3 '.1.5.1A 3.9.1.5.2A 3 '.1.5.3A CHAPTER 3

TABLE OF CONTENTS (Cont)

Title Structural Acceptance Criteria Materials, Quality Control, and Special Construction Techniques Concrete Reinforcing Steel Structural Steel Testing and Inservice Surveillance

'Requirements Foundations and Concrete Supports Description of the Foundation and Supports Reactor Building Foundations for Other Structures Applicable Codes, Standards, and Specifications Loads and Load Combinations Design and Analysis Procedures Structural Design Criteria Materials, Quality Control, and Special Construction Techniques Testing and Inservice Surveillance Requirements Reference MECHANICAL SYSTEMS AND COMPONENTS MECHANICAL SYSTEMS AND COMPONENTS (SWEC SCOPE OF SUPPLY)

Special Topics for Mechanical Components Design Transients Computer Programs Used in Analyses Experimental Stress Analysis Consideration for the Evaluation of the Faulted Condition Equipment and Components ASME III Compliance Piping Systems Analysis of Piping Systems Static Analysis Occasional Dynamic Loads Excluding Seismic and Hydrodynamic Inertia Loads

.Field-Run Piping Pacae 3.8-59 3.8-60 3.8-60 3.8-67 3.8-72 3.8-73a 3.8-73a 3.8-73a 3.8-74 3.8-74 3.8-75 3.8-75 3.8-76 3.8-77

,3.8-77 3.8-77 3.8-78 3.9A-1 3.9A-l 3.9A-1 3.9A-1 3.9A-1 3.9A-1 3.9A-l 3.9A-l 3.9A-1 3.9A-la 3.9A-2b 3.9A-3 3.9A-5 3.9A-6 USAR Revision 3-XV April 1989

Nine Mile Point Unit 2

FSAR CHAPTER 3

TABLE OF CONTENTS (Cont)

Section 3.9.1.5.4A 3.9 '.6A 3.9.2A 3.9.2.1A 3.9.2.1.1A 3.9.2.1.2A 3.9.2.1.3A 3.9.2.1.4A 3.9.2.1.5A 3.9.2.1.6A 3.9.2.2A 3.9.2.2.1A 3.9.2.2.2A 3.9.2.2.3A 3.9.3A 3.9.3.1A 3.9.3.1.1A 3.9.3.1.2A 3.9.3.1.3A 3.9.3.2A 3 '.3.2.1A 3.9.3.2.2A 3'.3 'A 3.9.3.4A 3.9.3.4.1A 3.9.3.4.2A 3.9.3.4.3A 3.9.4A 3.9.5A Title Load Combinations and Stress Criteria Safety-Related HVAC Ductwork and Supports Dynamic Testing and Analysis Piping Vibration, Thermal Expansion, and Dynamic Effects Flow Modes Preoperational Vibration Testing Preoperational Thermal Expansion Testing Measurement Locations Acceptance Criteria Corrective Actions Seismic Qualification of Safety-Related Mechanical Equipment Seismic Qualification Criteria Acceptance Criteria Seismic Qualification of Specific Non-NSSS Mechanical Equipment ASME Code Class 1,

2, and 3

Components, Component

Supports, and Core Support Structures Loading Combinations, Design Transients, and Stress Limits ASME Section III, Class 1 Components ASME Class 2 and 3 Components Compliance with Regulatory Guide 1.48 Pump and Valve Operability Assurance Pump Operability Program Valve Operability Program Design and Installation Details for Mounting of Pressure-Relief Devices Component Supports Pipe Supports Pump Supports Other Component Supports Control Rod Drive Systems Reactor Pressure Vessel Internals Pacae 3.9A-6 3.9A-6 3.9A-6 3.9A-6 3.9A;6a 3 'A-7 3.9A-7a 3.9A-8 3.9A-8 3.9A-8a 3.9A-9 3 'A-9 3.9A-ll 3.9A-12 3.9A-14 3.9A-14 3.9A-14a 3.9A-15a 3.9A-17 3.9A-17 3.9A-17 3.9A-19 3.9A-23 3.9A-23 3.9A-23a 3.9A-26 3.9A-26 3.9A-26b 3.9A-26c USAR Revision 3-xvi April 1989

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section Title PacCe 3.9.6A 3.9.6.1A 3.9.6.2A 3.9.6.3A 3.9.6.4A, Inservice Testing of Pumps and Valves Inservice Testing of Pumps Inservice Testing of Valves Relief Requests Pipe Welds Within Break Exclusion Area" 3.9A-26c 3.9A-26c 3.9A-27 3.9A-28 3.9A-28 3.9B 3.9.1B 3.9.1.1B 3.9.1.1.1B 3.9.1.1.2B 3.9.1.1.3B 3.9.1.1.4B 3.9.1.1.5B 3.9.1.1.6B 3.9.1.1.7B 3.9.1.1.8B 3.9.1.'1.9B 3.9.1.1.10B 3.9.1.1.11B 3.9.1.1.12B 3.9.1.2B 3.9.1.2.1B 3.9.1.2.2B 3.9.1.2.3B 3.9.1.2.4B 3.9.1.2.5B 3.9.1.2.6B 3.9.1.3B 3.9.1.3.1B 3.9.1.3.2B 3.9.1.4B MECHANICAL SYSTEMS AND COMPONENTS (GE SCOPE OF SUPPLY)

Special Topics for Mechanical Components Design Transients Control Rod Drive Transients Control Rod Drive Housing,and Incore Housing Transients Hydraulic Control Unit Transients Core Support and Reactor Internals Transients Main Steam System Transients Recirculation System Transients Reactor Assembly Transients Main Steam Isolation Valve Transients SafetylRelief Valve Transients Recirculation Flow Control Valve Transients Recirculation Pump Transients Recirculation Gate Valve Transients Computer Programs Used in Analysis Reactor Pressure Vessel and Internals Piping

~ Recirculation Pump Emergency Core Cooling System Pumps and Motors RHR Heat Exchangers Dynamic Load Analysis Experimental Stress Analysis Experimental Stress Analysis of Piping Components Orificed Fuel Support, Vertical and Horizontal Load Tests Considerations for the Evaluation of Faulted Conditions 3.9B-1 3.9B-1 3.9B-1 3.9B-1 3.9B-2 3.9B-3 3.9B-3 3.9B-3 3.9B-3 3.9B-4 3.9B-4 3.9B-4b 3.9B-6 3.9B-7 3.9B-7 3.9B-8 3.9B-9 3.9B-15 3.9B-16 3.9B-16a 3.9B-17 3.9B-18 3.9B-18 3.9B-18 3.9B-18 3.9B-19 USAR Revision 4

3 XV3.3.

October 1992

Nine Mi'le Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont) 28 Section 3.'9.1.4.1B 3.9.1.4.2B 3.9.1.4.3B 3.9.1.4.4B 3.9.1.4.5B 3.9.1.4.6B 3.9.1.4.7B 3.9.1.4.8B 3.9.1.4.9B 3.9.1.4.10B 3.9.1.4.11B 3.9.1.4.12B 3.9.2B 3.9.2.1B 3.9.2.1.1B 3.9.2.1.2B 3.9.2.1.3B 3.9.2.1.4B 3.9.2.1.5B 3.9.2.1.6B 3.9.2.2B 3.9.2.2.1B 3.9.2.2.2B Title Control Rod Drive System Components Standard Reactor Internal Components Reactor Pressure Vessel Assembly Core Support Structure Recirculation Gate, Safety/

Relief Valves, and Main Steam Isolation Valves Recirculation System Flow Control Valve Recirculation Piping Nuclear Steam Supply System

Pumps, Heat Exchanger, and Turbine Control Rod Drive Housing Supports Fuel Storage Racks Fuel Assembly (Including Channels)

Refueling Equipment Dynamic Testing and Analysis Piping Vibration, Thermal Expansion, and Dynamic. Effects Piping Vibration Thermal Expansion Testing of Recirculation Piping Dynamic Effects Testing of Main Steam and Recirculation Piping Test Evaluation and Acceptance Criteria for Recirculation Piping Corrective Actions for Recirculation Piping Measurement

.Locations for Recirculation Piping Seismic and Hydrodynamic Qualification of Safety-Related Mechanical Equipment Tests and Analysis Criteria and Methods Seismic and Hydrodynamic Ioad Qualification of Specific NSSS Mechanical Components Pacae 3.9B-19 3.9B-20 3.9B-21 3.9B-21 3.9B-21a 3.9B-2la 3.9B-22 3.9B-22 3.9B<<22 3.9B-22 3.9B-22 3.9B-22 3.9B-23 3.9B-23 3.9B-23 3.9B-24 3.9B-25 3.9B-26 3.9B-27 3.9B-28 3.9B-28 3.9B-29 3.9B-31 Amendment 28 3-xviii May 1987

Nine Mile Point Unit 2 FSAR Section 3.9.2.3B 3.9.2.4B 3.9.2.5B 3.9.2.6B 3.9.3B 3.9.3.1B 3.9.3.1:1B 3.9.3.1.2B 3.9.3.1.3B 3.9.3.1.4B 3.9.3.1.5B 3.9.3.1.6B 3.9.3.1.7B 3.9.3.1.8B 3.9.3.1.9B 3.9.3;1.10B 3.9.3.1.11B 3.9.3.1.12B 3.9.3.1.3.3B

.3.9.3.1.14B 3.9.3.2B 3.9.3.2.1B 3.9.3.2.2B 3.9.3.2.3B CHAPTER 3 TABLE OF CONTENTS (Cont)

Title Dynamic Response of Reactor Internals Under Operational Flow Transients and Steady-State Conditions Preoperational Flow-Induced Vibration Testing of Reactor Internals Dynamic System Analysis of Reactor Internals Under Faulted Conditions Correlations of.Reactor Internals Vibration Tests With Analytical Results ASME Section III, Safety Class 1,

2, and 3 Components, Component

Supports, and Core Support Structures Load Combinations, Design Transients, and Stress Limits Plant Conditions Reactor Pressure Vessel Assembly Main Steam Piping Recirculation Loop Piping Recirculation System Valves

+ Recirculation Pump Standby Liquid Control Tank Residual Heat Removal Heat Exchangers RCIC Turbine RCIC Pump ECCS Pumps Standby Liquid Control Pump Main Steam Isolation and Safety/Relief Valves Reactor Water Cleanup System Pump and Heat Exchangers Pump and Valve Operability Assurance ECCS Pumps and Motors SLC Pump and Motor Assembly and RCIC Pump Assembly NSSS Valves Pacae 3.9B-34 3.9B-36 3.9B-37 3.9B-38 3.9B-38 3.9B<<38 3.9B-39'.9B-41 3.9B-42 3.9B-42 3.9B-42 3.9B-42 3.9B-43 3.9B-43 3.9B-43 3.9B-44 3.9B-44 3.9B 45 3.9B-45 3.9B-46 3.9B-46 3.9B-46 3.9B-49 3.9B-49a 28 Amendment 28 3-.xix May 1987

Nine Mile Point Unit 2 FSAR CHAPTER 3 TABLE OF CONTENTS (Cont'd)

Section 3.9.3.3B 3.9.3.3.1B 3.9.3.4B 3.9.3.4.1B 3.9.3.4.2B 3.9.3.4.3B 3.9.3.4..4B 3.9.3.4.5B 3.9.4B 3.9.4.1B 3.9.4.2B 3.9.4.3B 3.9.4.4B 3.9.5B 3.9.5.1B 3.9.5.1.1B 3.9.5.1.2B 3.9.5.2B 3.9.5.2.1B 3.9.5.2.2B 3.9.5.2.3B 3.9.5.3B 3.9.5.3.1B 3.9.5.3.2B 3.9.5.3.3B 3.9.5.3.4B 3.9.5.3.5B 3.9.5.3.6B 3.9.6B Title Design and Installation of Pressure Relief Devices Main Steam Safety/Relief Valves Component Supports Piping Reactor Pressure Vessel Support Skirt and Stabilizer NSSS Floor-Mounted Equipment (Pumps, Heat Exchanger, and RCIC Turbine)

Supports for ASME Safety Class 1,

2, and 3 Active Components Bolting Support Control Rod Drive System Descriptive Information on CRD System Applicable CRD System Design Specifications Design Loads, Stress Limits, and Allowable Deformation CRD Performance Assurance Program Reactor Core Support Structures and Pressure Vessel Internals Design Arrangements Core Support Structures Reactor Vessel Internals Design Loading Conditions Events to Be Evaluated Pressure Differential During Rapid Depressurization Recirculation Line and Steam Line Break Design Bases Safety Design Bases Power Generation Design Bases Design Loading Categories

Response

of Internals Due to Inside Steam Break Accident

Stress, Deformation, and Fatigue Limits for Engineered Safety Feature Reactor Internals (Except Core Support Structure)
Stress, Deformation, and Fatigue Limits for Core Support Structures References Pacae
3. 9B-51
3. 9B-51
3. 9B-51
3. 9B-51 3.9B-55 3.9B-55 3.9B-55 3.9B-56 3.9B-56

.3.9B-56 3.9B-56 3.9B-57 3.9B-58 3.9B-58 3.9B-58 3.9B-60 3.9B-62 3.9B-66 3.9B-66 3.9B-67 3.9B-67 3.9B-69 3.9B-69 3.9B-69 3.9B-70 3.9B-70 3.9B-71

3. 9B-71 3.9B-72 USAR Revision 4

3 xx October 1992

Nine Mile Point Unit 2 FSAR Section 3.10 3.10A 3.10 'A 3.10.2A 3.10.2.1A F 10.2 'A 3.10.2.3A 3.10.2.4A 3.10.3A 3.10.4A 3.10B 3.10.1B 3.10.1.1B 3.10.1.2B 3.10.1.2.1B F 10.2B 3.10.2.1B 3.10.2.2B 3.10.2.3B 3.10.2.4B CHAPTER 3 TABLE OF CONTENTS (Cont)

Title SEISMIC QUALIFICATION OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT SEISMIC QUALIFICATION OF CATEGORY I INSTRUMENTATION AND ELECTRICAL EQUIPMENT (SWEC SCOPE OF SUPPLY)

Seismic Qualification Criteria Methods and Procedures for Qualifying Electrical Equipment and Instrumentation Testing Prototype Testing Analysis Combined Analysis and Testing Methods and Procedures of Analysis or Testing of Supports of Electrical Equipment and Instrumentation Operating License Review SEISMIC AND HYDRODYNAMIC QUALIFICA-TIONS OF SEISMIC CATEGORY I INSTRU-MENTATION AND ELECTRICAL EQUIPMENT (GE SCOPE OF SUPPLY)

Dynamic Qualification Criteria Seismic Category I Equipment Identification Dynamic Design Criteria NSSS Equipment Methods and Procedures for Qualifying Electrical Equipment and Instrumentation Methods of Showing NSSS Equipment Compliance with IEEE-344-1975 and Regulatory Guide 1.100 Testing Procedures for Qualifying Electrical Equipment and Instrumentation Qualification of Valve Operators Qualification of NSSS Motors

~Pa e

3.10A-1 3.10A-1 3.10A-1 3.10A-2 3.10A-3 3.10A-4 3.10A-4 3.10A-4 3.10A-4 3.10A-5 3.10B-1 3.10B-1 3.10B-1 3.10B-1 3.10B-1 3

~ 10B 2 l zu I 24 3.10B-2 3

~ 10B-3 I ~4 3.10B-4 3.10B-S Amendment 24 3-xxi February 1986

Nine Mile Point Unit 2 FSAR 24 24 f

Section

3. 10

~ 3B 3.10.3.1B 3.10.3.1.1B 3.10.4B 3.11 3.11.1

3. 11

~ 2

~

3.11.2.1 3.11.2.2 3.11.3 3.11.4 3.11.5 CHAPTER 3

TABLE OF CONTENTS (Cont)

Title Methods and Procedure of Analysis or Testing of Supports of Electrical Equipment and Instrumentation Dynamic 'Analysis and Testing Procedures Panel-Mounted Equipment Operating License Review ENVIRONMENTAL DESIGN OF MECHANICAL AND ELECTRICAL EQUIPMENT Equipment Identification and Environmental Conditions Qualification Tests and Analyses Qualification Method of.Qualification of Class.lE Equipment and Components Qualification Test Results Loss of Heating, Ventilation, and Air Conditioning Estimated Chemical and Radiation Environment Pacae 3.10B-S 3.10B-S 3 '0B-5 3.10B-6 3.11-1 F 11-1, 3.11-la 3.ll-.la 3.11-2 3.11-4 3.11-4 3.11-5 Amendment 24 3-XXii February 1986

Nine Mile Point Unit 2 FSAR CHAPTER 3

TABLE OF CONTENTS (Cont)

Section 3.11.5.1 3.11.5.2 3.11.6 3.11.7 APPENDIX 3A-APPENDIX 3B APPENDIX 3C APPENDIX 3D Title Chemical Environment Radiation Environment Submergence References COMPUTER PROGRAMS FOR DYNAMIC AND STATIC ANALYSIS OF CATEGORY I STRUCTURES~

EQUIPMENTS AND COMPONENTS PRESSURE ANALYSIS FOR SUBCOMPARTMENTS OUTSIDE CONTAINMENT FAILURE MODE ANALYSIS FOR PIPE BREAKS AND CRACKS UNIT 2 ASSESSMENT OF GENERAL DESIGN CRITERIA 51 TO 10CFR50 Pacae 3.11-5 3.11-6 3.11-6 F 11-7 APPENDIX 3E CLASSIFICATION OF STRESSES IN COMPONENT/PIPING SUPPORTS DUE TO LOADS FROM SEISMIC ANCHOR MOTION AND THERMAL GROWTH OF PIPING USAR Revision 0

3-xxiii April 1989

Nine Mile Point Unit 2 FSAR CHAPTER 3

LIST OF TABLES Table

Number, 3

~ 2 1

3.2-2 3

~ 2 3

3.2-4

3. 3-1 3.4-1 3.4-2 3.4-3
3. 4-4 EQUIPMENT AND STRUCTURE CLASSIFICATION CODE GROUP DESIGNATIONS, INDUSTRY CODES, AND STANDARDS FOR MECHANICAL COMPONENTS

SUMMARY

OF SAFETY CIASS DESIGN REQUIREMENTS REACTOR COOLANT PRESSURE BOUNDARY CLASS 1

EQUIPMENT CODE AND ADDENDA APPLICATION DYNAMIC WIND PRESSURE FOR CATEGORY I STRUCTURES FLOOD PROTECTION FOR SAFETY-RELATED STRUCTURES AND SYSTEMS

  • 4 PENETRATIONS THROUGH EXTERIOR WALLS OF REACTOR BUILDING BELOW DBFL PENETRATIONS THROUGH EXTERIOR WALLS OF CONTROL AND TURBINE BUILDINGS BELOW DBFL PENETRATIONS THROUGH EXTERIOR WALLS OF RADWASTE BUILDING AND SCREENWELL BUILDING BELOW DBFL 3.4-5 3.4-6
3. 4-7 3.5-1
3. 5-2 PENETRATIONS THROUGH EXTERIOR WALLS OF PIPE TUNNELS BELOW DBFL PENETRATIONS THROUGH EXTERIOR WALLS OF DIESEL GENERATOR BUILDING AND MAIN STACK BELOW DBFL PERFORMANCE OF WATER STOP MATERIAL IN EXPECTED ENVIRONMENT STRUCTURES,
SYSTEMS, AND COMPONENTS SAFETY-RELATED

SUMMARY

OF FORCES AND STRESSES ACTING ON THERMOWELL WELDS IN THE VARIOUS HIGH ENERGY SYSTEMS Amendment 7

3-xxiv December 1983

Nine Mile Point Unit 2 FSAR Table Number LIST OF TABLES (Cont)

Title

3. 5-3 DAMAGE PROBABILITY DUE TO LON TRAJECTORY TURBINE MISSILES FROM UNIT 2 STRIKING PLANT REGIONS AT UNIT 2 (Manufacturer's Probability)

Amendment 7

3-xxiva December 1983

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLYBLANK Amendment 7

3-xxivb December 1983

Nine Mile Point Unit 2 FSAR Table Number 3.5-4 3.5-5 3.5-6 3.5-7 3.5-8 3.5-9 3.5-10 3.5-11 3.5-12 CHAPTER 3

IIST OF TABLES (Cont)

Title DAMAGE PROBABIIITY DUE TO'LOW TRAJECTORY TURBINE MISSILES FROM UNIT 1 STRIKING PLANT REGIONS AT. UNIT 2 (Manufacturer's Probability)

DAMAGE PROBABILITY DUE TO LOW TRAJECTORY TURBINE MISSIIES 'FROM JAMES A. FITZPATRICK POWER STATION STRIKING PLANT REGIONS AT UNIT 2 (Manufacturer's Probability)

DAMAGE PROBABILITY DUE TO LOW TRAJECTORY TURBINE MISSILES FROM UNIT 2 STRIKING PIANT REGIONS AT UNIT 2 (NRC Probability)

DAMAGE PROBABILITY DUE TO LOW TRAJECTORY TURBINE MISSILES FROM UNIT 1 STRIKING PLANT REGIONS AT UNIT 2 (NRC Probability)

DAMAGE PROBABILITY DUE TO LOW TRAJECTORY TURBINE MISSILES FROM JAMES A. FITZPATRICK POWER STATION STRIKING PLANT REGIONS AT UNIT 2 (NRC Probability)

DAMAGE PROBABILITY DUE TO HIGH TRAJECTORY TURBINE MISSILES FROM UNIT 2 STRIKING PLANT REGIONS AT UNIT 2 (Manufacturer's Probability)

DAMAGE PROBABILITY DUE TO HIGH TRAJECTORY TURBINE MISSILES FROM UNIT 1 STRIKING PLANT REGIONS AT UNIT 2 (Manufacturer's Probability)

DAMAGE PROBABILITY DUE TO HIGH TRAJECTORY TURBINE MISSIIES FROM JAMES A. FITZPATRICK POWER STATION STRIKING PLANT REGIONS AT UNIT 2 (Manufacturer's Probability)

DAMAGE PROBABILITY DUE TO HIGH TRAJECTORY TURBINE MISSILES FROM UNIT 2 STRIKING PLANT REGIONS AT UNIT 2 (NRC Probability) 3 XXV

Nine Mile Point Unit 2 FSAR CHAPTER 3 LXST OF TABLES (Cont'd)

Table Number Title 3.5-13 3.5-14 3.5-15 3.5-16 3.5-17 DAMAGE PROBABXLXTY DUE TO HIGH TRAJECTORY TURBINE MZSSILES FROM UNIT 1 STRIKING PLANT REGIONS AT UNIT 2 (NRC Probability)

DAMAGE PROBABILITY DUE TO HXGH TRAJECTORY TURBINE MISSILES FROM JAMES A. FITZPATRICK POWER STATION STRIKING PLANT REGIONS AT UNIT 2 (NRC Probability)

SUM OF DAMAGE PROBABXLITY DUE TO LOW AND HIGH TRAJECTORY TURBINE MISSILES GENERATED FROM TURBINES AT UNXTS 1 AND 2 AND JAMES A. FITZPATRICK TO PLANT REGIONS OF UNIT 2 (Manufacturer's Probability)

SUM OF DAMAGE PROBABZLXTY DUE TO LOW AND HXGH TRAJECTORY TURBINE MISSILES GENERATED FROM TURBINES AT UNITS 1 AND 2 AND JAMES A. FITZPATRICK TO PLANT REGIONS OF UNIT 2 (NRC Probability)

TURBINE MISSILE INFORMATION (43-INCH STAGE BUCKET UNXT

3. 5-18 TURBINE MISSILE INFORMATION (38-INCH LAST STAGE BUCKET UNXTS 3.5-19

. 3.5-20 3.5-21 3.5-22 BASIC ASSUMPTIONS FOR PROBABILXTY ANALYSIS OF TURBINE MXSSILE STRIKE DELETED SELECTED EXTERNAL MISSILES MISSILE BARRIERS FOR NATURAL PHENOMENA AND TURBINE-GENERATED MISSILES

3. 6A-1 3.6A-2 COMPARISON OF PIPE RUPTURE CRXTERIA

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPXNG Main Steam System Xnside Containment North Inner Loop USAR Revision 4

3 zxvi October 1992

Nine Mile Point Unit 2 FSAR Table Number 3.6A-3

3. 6A-4 3.6A-5
3. 6A-6 3.6A-7 3.6A-8 3.6A-9 3.6A-10 3.6A-ll
3. 6A-12

.. CHAPTER 3 LIST OF TABLES (Cont)

Title

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam System-Inside Containment North Outer Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam System Inside Containment South Inner Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam System Inside Containment South Outer Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2 AND 3 PIPING Main Steam System - Outside Containment North Outer Loop.,

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2 AND 3 PIPING Main Steam System Outside Containment North Inner Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2 AND 3 PIPING Main Steam System Outside Containment South Outer Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2 AND 3 PIPING Main Steam System - Outside Containment South Inner Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam Syst: em-Vent, (Inside Containment)

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam System-SRV (Inside Containment)

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Main Steam Drains Inside Containment Amendment 12 3-XXVii June 1984

Nine Mile Point Unit 2 FSAR Table Number CHAPTER 3 LIST OF TABLES (Cont)

Title 3.6A-13 3.6A-14 3.6A-15 3.6A-16 3.6A-17

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Feedwater System Inside Containment South Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Feedwater System Inside Containment North Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2 AND 3 PIPING - Feedwater System Outside Containment North Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 2

AND 3 PIPING Feedwater System Outside Containment - South Loop

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Reactor Core Isolation Cooling and Reactor Head Spray-Inside Containment 3.6A-18

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CIASS 2

AND 3 PIPING Reactor Core Isolation Cooling and RHS Outside Containment 3 'A-19 3.6A-20 3.6A-21

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING High-Pressure Core Spray Inside Containment

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Low-Pressure Core Spray Inside Containment

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Residual Heat Removal System Shutdown Mode Inside Containment 3.6A-22

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CIASS 1 PIPING Residual Heat Removal System (LPCI Mode)

I'nside Containment Amendment 12 3-zxviii June 1984

Nine Mile Point, Unit 2 FSAR CHAPTER 3 LIST OF TABLES (Cont)

Table Number 3.6A-23 3.6A-24

3. 6A-25
3. 6A-26 3.6A-27 3.6A-28 3

~ 6A-29 3.6A-30 3.6A-31 3.6A-32 Title

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Reactor Recirculation Piping System (RCS)

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Reactor Water Cleanup System Inside Containment

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 3

AND 4 PIPING Reactor Water Cleanup System Outside Containment

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CLASS 1 PIPING Standby Liquid Control Inside Containment,

SUMMARY

OF STRESSES IN HIGH ENERGY ASME SAFETY CIASS 1 PIPING Control Rod Drive Outside Containment

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Main Steam System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Main Steam System (Outside Containment)

MAIN STEAM VENT LINE

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Main Steam Safety Relief Valve

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Main Steam Drains Inside Containment Amendment 12 3-XXiX June 1984

Nine Mile Point Unit 2 FSAR CHAPTER 3 Table Number LIST OF TABLES (Cont)

Title 3.6A-33

3. 6A-34
3. 6A-35 3.6A-36 3.6A-37 3.6A-38
3. 6A-39 3.6A-40 3.6A-41
3. 6A-42 3.6A-43

SUMMARY

OF ANALYSIS OF PIPING FAIjURE AS A RESULT OF PIPE WHIP Main Steam Drain Lines:

Piping Outboard of Jet Impingement Wall

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Feedwater System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Feedwater System (Outside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Reactor Core Isolation Cooling System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP ICS Head Spray

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Residual Heat, Removal (Outside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP High-Pressure Core Spray System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Low-Pressure Core Spray System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Residual Heat Removal System Shutdown Mode

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Residual Heat Removal System (LPCI Mode)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Recirculation System Amendment 12 3-XXX June 1984

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF TABLES (Cont)

Table Number Title 3.6A-44 3.6A-45 3.6A-46 3.6A-47 3.6A-48 3.6A-49 3.6A-50 3.6A-51 3.,6A-52 3.6A-53

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESUIT OF PIPE WHIP - Reactor Water Cleanup System

( Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAIjURE AS A RESULT OF PIPE WHIP - Reactor Water Cleanup System (Outside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Standby Liquid Control System

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Control Rod Drive System

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Main Steam System (Inside Containment)

North Loop

SUMMARY

OF ANALYSIS OF TARGETS AS A RESUIT OF JET IMPINGEMENT - Main Steam System (Inside Containment)

South Loop

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Main Steam System (Outside Containment)

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT - Main Steam Vent Line

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Main Steam Safety Relief'alve

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Main Steam Drains Inside Containment West Loop Amendment 12 3-XXX1 June 1984

Nine Mile Point Unit'2 FSAR CHAPTER 3 LIST OF TABLES (Cont)

Table Number 3.6A-54 3.6A-55 Title

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGENENT 3.6A-56 3.6A-57 3.6A-58 3.6A-59 3.6A-60 3.6A-61

3. 6A-62
3. 6A-63 3.6A-64

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Main Steam Drain Lines:

Piping Outboard of Jet Impingement Wall

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Feedwater System (Inside Containment,)

South Loop

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Feedwater System (Inside Containment)

North Loop

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Feedwater System (Outside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF JET IMPINGEMENT Reactor Core Isolation Cooling System (Inside Containment)

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Reactor Core Isolation Cooling System (Outside Containment)

SUMNARY OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGENENT High Pressure Core Spray System

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGENENT Low-Pressure Core Spray System (Inside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE. AS A RESULT OF JET IMPINGEMENT Residual Heat Removal System Shutdown Mode Amendment 12 3-xxxii June 1984

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF TABLES (Cont)

Table Number Title 3.6A-65 3.6A-66 3.6A-67 3.6A-68 3.6A-69 3.6A-70 3.6A-71 3.6A-72 3.6A-73 3.6B-l 3.6B-2 3.7A-1 3.7A-2 3.7A-3 Amendment 21 DAMPING FACTORS FOUNDATION/SUPPORT MEDIA FOR CATEGORY 1

STRUCTURES PRIMARY CONTAINMENT MODE SHAPES (CRACKED) 3-xxx3.3.a September 1985

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Residual Heat Removal System (Low-Pressure Coolant Injection Mode)

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Recirculation System (North Loop)

SUMMARY

OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Recirculation System (South Loop)'UMMARY OF ANALYSIS OF TARGETS AS A RESULT OF JET IMPINGEMENT Reactor Water Cleanup System

( Inside Containment)

SUMMARY

OF ANAIYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP - Reactor Water Cleanup System (Outside Containment)

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Standby Liquid Control System

SUMMARY

OF ANALYSIS OF PIPING FAILURE AS A RESULT OF PIPE WHIP Control Rod Drive System ESSENTIAL SYSTEMS/COMPONENTS/EQUIPMENT EVALUATED FOR PIPE FAILURES HIGH ENERGY PIPING PDA VERIFICATION RESTRAINT DATA COMPARISON OF PDA AND NSC CODE

Nine Nile Point Unit 2 FSAR THIS PAGE INTENTIONALLYBLANK Amendment 12 3-xxxiib June 1984

Nine Mile Point Unit 2

FSAR Table Number 3.7A-4 3.7A-5 3.7A-6 3.7A-7 3.7A-8 3.7A-9 3.7A-10 3.7A-ll 3.7A-12 3.7A-13 3.7B-l 3.7B-2 3.8-1 3.8-2 CHAPTER 3

LIST OF TABLES (Cont)

Title PRIMARY CONTAINMENT MODE SHAPES (UNCRACKED)

SECONDARY CONTAINMENT MODE SHAPES CONTROL AND DIESEL GENERATOR BUILDING MODE SHAPES PRIMARY CONTAINMENT MODAL RESPONSES (CRACKED)

PRIMARY CONTAINMENT MODAL RESPONSES (CRACKED)

SSE ACCELERATION COMPARISON TABULATION OF STRUCTURAL GAP AND WORST-CONDITION GAP FOR SSE COMPARISON DESIGN ATTRIBUTES TO BE REVIEWED FOR VERIFICATION OF LARGE BORE SAFETY-RELATED PIPING AS REQUIRED BY NRC IE BULLETIN 79-14 DESIGN ATTRIBUTES TO BE REVIEWED FOR VERIFICATION OF SMALL BORE SAFETY-RELATED PIPING AS REQUIRED BY NRC IE BULLETIN 79-14 COMPARISON OF RESULTS:

STATIC VERSUS DYNAMIC ANALYSIS FOR INSTRUMENT PANEL 2DFM-PNL102 CRITICAL DAMPING RATIOS FOR DIFFERENT MATERIALS NUMBER OF DYNAMIC

RESPONSE

CYCLES EXPECTED DURING A SEISMIC EVENT LOAD COMBINATIONS FOR CONCRETE PRIMARY CONTAINMENT LOAD COMBINATIONS FOR CONTAINMENT WALL LINERS FLOOR LINERS CORNER TRANSITION REGIONS'ND EMBEDMENT LINER INSERT PLATES 3.8-3 LOAD COMBINATIONS FOR ACCESS LOCKS AND HATCHES USAR Revision 0

3 XXXi11 April 1989

Nine Mile Point Unit 2 FSAR Table Number 3.'8-4 3.8-5 3.8-6 3.8-7 3.8-8 CHAPTER 3 LIST,OF TABLES (Cont)

Title LOAD COMBINATIONS FOR THE,DRYWELL HEAD LOAD 'COMBINATIONS AND STRESS LIMITS FOR SAFETY CLASS 1 PIPE PENETRATIONS LOAD COMBINATIONS AND STRESS LIMITS FOR SAFETY CIASS 2 PIPE PENETRATIONS LOAD COMBINATIONS AND STRESS LIMITS FOR PENETRATIONS - CLASS MC PORTIONS STRESS Amendment 25 3-xxxiiia March 1986

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLYBLANK Amendment 5

3-xxxiiib October 1983

Nine Mile Point Unit 2 FSAR Table Number CHAPTER 3 LIST OF TABLES (Cont)

Title 3.8-9 3.8-10 3.8-11 3.8-12 3.8-13 3.8-14 3.8-15 LOAD COMBINATIONS FOR THE BIOLOGICAL SHIELD WALL DESIGN STRENGTH FOR LOAD COMBINATIONS ON CATEGORY I STEEL STRUCTURES LOAD COMBINATIONS FOR CATEGORY I STEEL STRUCTURES LOAD COMBINATIONS FOR INTAKE TUNNELS MAJOR STRUCTURES FOUNDATION SYSTEMS FACTORS OF SAFETY FOR OVERTURNING, SLIDING, AND FLOTATION OF MAJOR CATEGORY I STRUCTURES PREDICTED STRUCTURAL RESPONSE CONTAINMENT PRESSURE TEST 3.9A-l 3.9A-2 3.9A-3 3.9A-4 3.9A-5 I

3.9A-6 3.9A-7 TRANSIENTS AND THE NUMBER OF ASSOCIATED CYCLES CONSIDERED IN THE DESIGN AND FATIGUE ANALYSIS OF CLASS 1 PIPING LOAD COMBINATIONS AND STRESS LIMITS FOR PIPE STRESS ANALYSIS PIPE STRESS ANALYSIS CLASSIFICATIONS FOR ASME CODE CIASSES 1, 2, 3

MECHANICAL EQUIPMENT QUALIFICATION RESULTS LOAD COMBINATIONS FOR ASME SECTION III CLASS 1 VALVES LOAD COMBINATIONS FOR ASME SECTION III CLASS 2 AND 3 AND NON-ASME COMPONENTS STRESS LIMITS FOR ASME SECTION III CLASS 1

(NB) SEISMIC CATEGORY I COMPONENTS (ELASTIC ANALYSIS)

Amendment 24 3 XXX1V February 1986

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF TABLES (Cont'd.)

Table Number 3.9A-11 3.9A-12 3.9A-13 3.9A-14 3.9A-15 3.9A-16 3.9B-1 Title

SUMMARY

OF SEISMIC STRESS ANALYSIS RESULTS ACTIVE VALVES (BOP)

LOAD CONDITIONS FOR COMPONENT SUPPORTS AND STRESS LIMITS FOR PLATE AND SHELL-TYPE, SUPPORTS LOAD CONDITIONS FOR PIPE SUPPORTS REQUIREMENTS FOR SAFETY'LASSES 2 AND 3 INSTRUMENT AND PNEUMATIC TUBING AND SUPPORTS BASIS FOR DESIGN AND CONSTRUCTION OF ASME AND NON-ASME PIPING SUPPORTS I

PLANT EVENTS 3.9B-2

3. 9B-2a 3.9B-2b 3.9B-2c 3.9B-2d 3.9B-2e
3. 9B-2f
3. 9B-29 3.9B-2h
3. 9B-2i
3. 9B-2g LOAD COMBINATIONS'TRESS LIMITS~ AND ALLOWABLE STRESSES CONTROL ROD DRIVE CONTROL ROD GUIDE TUBE INCORE HOUSING JET PUMPS A

HIGHEST STRESSED REGION ON THE LPCI COUPLING (ATTACHMENT RING)

REACTOR PRESSURE VESSEL SUPPORT EQUIPMENT CONTROL ROD DRIVE HOUSING REACTOR PRESSURE VESSEL AND SHROUD SUPPORT ASSEMBLY REACTOR VESSEL INTERNALS AND ASSOCIATED EQUIPMENT SAFETY/RELIEF VALVES SPRING-LOADED DIRECT ACTING TYPE 3.9B-2k 3.9B-21 REACTOR RECIRCULATION SYSTEM GATE VALVES RECIRCULATION FLOW CONTROL VALVE 24-IN SIZE (FISHER)

USAR Revision 5

3-xxxv October 1993

Table Number 3.9B-2m 3.9B-2n 3.9B-2o 3.9B-2p 3.9B-2q 3.9B-2r 3.9B-2s 3.9B-2t.

3.9B-2u 3.9B-2v 3.9B-2w 3.9B-2x 3.9B-2y as 3.9B-2z 3.9B-3 3.9B-4 3;9B-5 3.9B-6 3.9B-7 3.9B-8 Nine Mile Point'. Unit. 2 FSAR CHAPTER 3 ZIST OF TABZES (Conh)

Title ASME SAFETY CLASS 1 RECIRCULATION PIPING AND PIPE MOUNTED EQUIPMENT HIGHEST STRESS

'UMMARY REACTOR REFUELING AND SERVICING EQUIPMENT FUEZ ASSEMBZ Y ( INCZUDING CHANNEL)

RECIRCULATION PUMP STANDBY LIQUID CONTROL TANK RESIDUAL HEAT REMOVAL HEAT EXCHANGER RCIC TURBINE RCIC PUMP ECCS PUMPS STANDBY LIQUID CONTROL PUMP REACTOR WATER CLEANUP SYSTEM PUMP REACTOR WATER CZEANUP CRD HOUSING SUPPORTS MAIN STEAM ISOLATION VALVES NSSS COMPLIANCE WITH REGULATORY GUIDE 1.48 GE-SUPPLIED SEISMIC ACTIVE PUMPS AND VAZVES DEFORMATION LIMIT (FOR SAFETY CLASS REACTOR INTERNAL STRUCTURES ONLY)

PRIMARY STRESS. LIMIT (FOR SAFETY CLASS

'REACTOR INTERNAL STRUCTURES ONZY)

BUCKLING STABILITY LIMIT (FOR SAFETY CLASS REACTOR INTERNAL STRUCTURES ONLY)

FATIGUE I IMIT.(FOR SAFETY CLASS REACTOR INTERNAL STRUCTURES ONZY)

Amendmenh 28 3-xxxvi May 1987

Table Number 3.9B-9 Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF TABLES (Cont)

Title CORE SUPPORT STRUCTURES STRESS CATEGORIES AND LIMITS OF STRESS INTENSITY FOR SERVICE LEVELS A AND B (NORMAL AND UPSET)

CONDITIONS 3.9B"10 CORE SUPPORT STRUCTURES STRESS CATEGORIES AND LIMITS OF STRESS INTENSITY FOR SERVICE LEVEI C

(EMERGENCY) CONDITIONS 3.9B-11 3.10A-1 CORE SUPPORT STRUCTURES STRESS CATEGORIES AND LIMITS OF STRESS INTENSITY FOR SERVICE LEVEI D (FAUIT) CONDITION CLASS 1E ELECTRICAL EQUIPMENT QUALIFICATION RESULTS 3.10B-1 3.10B-2 ESSENTIAL ELECTRICAL COMPONENTS AND INSTRU-MENTS SEISMIC QUALIFICATION TEST

SUMMARY

DELETED Amendment 24 February 1986

Nine Mile Point Unit 2 FSAR CHAPTER 3

LIST OF FIGURES Figure Number Title 3.2-1 3

~ 3 1

3.5-1 3.5-2 3.5-3

3. 5-4 3.5-5 GROUP CLASSIFICATION DIAGRAM ANNUAL EXTREME WIND VELOCITY 30 FT ABOVE GROUND, 100-YR MEAN'RECURRENCE INTERVAL TURBINE PLACEMENT AND ORIENTATION TURBINE MISSILE REFERENCED COORDINATE SYSTEM SOLID ANGLE ON A UNIT SPHERE TOP VIEW OF IDEALIZED'ARGET SIDE VIEW OF IDEALIZED TARGET 3.6A-1 3.6A-2 3.6A-3 3.6A-4 3.6A-5 3.6A-6 3.6A-7 3.6A-8 3.6A-9 3.6A-10 3.6A-11

AREAS OF ANALYSIS STEADY STATE BLOWDOWN FORCES VS FRICTION PARAMETER DYNAMIC ANALYSIS MODEL RHS (LPCI) RESTRAINT 2RHS*PRR004 FLUID BLOWDOWN FORCES USED FOR 2RHS*PRR004 RESTRAINT ANALYSIS RESTRAINT (2RHS*PRR004)

REACTION LOAD ENERGY BALANCE SAMPLE PROBLEM PIPE CRUSH BUMPER TWO-PIN LAMINATED PIPE RUPTURE RESTRAINT (SMALL LINES)

TWO-PIN LAMINATED PIPE RUPTURE RESTRAINT (LARGE LINES)

OMNI'-DIRECTIONAL PIPE RUPTURE RESTRAINT LIMIT STOP RESTRAINT Amendment, 24 3-xxxvil.3.

February 1986

Nine Mile Point Unit 2 FSAR Figure Number CHAPTER 3

.LIST OF FIGURES (Cont)

Title

.3.6A-12

3. 6A-13 3.6A-14

'3.6A-15 3.6A-16 HIGH ENERGY PIPE BREAKS MAIN STEAM NORTH INNER AND OUTFR LOOPS, INSIDE CONTAINMENT HIGH ENERGY PIPE

BREAKS, MAIN STEAM SOUTH INNER AND OUTER LOOPS, INSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS MAIN STEAM NORTH AND SOUTH LOOPS, OUTSIDE CONTAINMENT HIGH ENERGY, PIPE
BREAKS, MAIN STEAM VENT LINE, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, MAIN STEAM SAFETY RELIEF VALVE SYSTEM, INNER AND OUTER LOOPS, INSIDE CONTAINMENT
3. 6A-17

'.6A-18 3.6A-19 3.6A-20

3. 6A-21 3.6A-22 3.6A-23 3.6A-24 HIGH ENERGY PIPE
BREAKS, MAIN STEAM SAFETY RELIEF VALVE SYSTEM, INNER AND OUTER LOOPS, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, MAIN STEAM DRAIN
LINES, INSIDE CONTAINMENT (SHEETS 1

THROUGH 6)

HIGH ENERGY PIPE

BREAKS, FEEDWATER NORTH
LOOP, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, FEEDWATER, SOUTH
LOOP, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, FEEDWATER, NORTH AND SOUTH LOOPS, OUTSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR CORE ISOLATION COOLING, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR CORE ISOLA-TION COOIING HEAD SPRAY, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR CORE ISOLA-TION COOLING AND RHS, OUTSIDE CONTAINMENT Amendment 24 3-xzxlx February 1986

Nine Mile Point Unit 2 FSAR CHAPTER 3 Figure Number

3. 6A-25
3. 6A-26 3.6A-27 LIST OF FIGURES (Cont)

Title HIGH ENERGY PIPE

BREAKS, HIGH PRESSURE CORE
SPRAY, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, LOW PRESSURE CORE
SPRAY, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, RESIDUAL HEAT REMOVAL -

SHUTDOWN MODE, INSIDE CONTAINMENT 24

3. 6A-28 3.6A-29 3.6A-30
3. 6A-31
3. 6A-32 3.6A-33 3.6A-34 3.6A-3S
3. 6A-36
3. 6A-37
3. 6A-38 HIGH ENERGY PIPE
BREAKS, RESIDUAL HEAT REMOVAL LPCI
MODE, INSIDE CONTAINMENT RECIRCULATION SYSTEM RECIRCULATION SYSTEM HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, INSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS; REACTOR WATER
CLEANUP, OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS,, REACTOR WATER
CLEANUP, OUTSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, OUTSIDE CONTAINMENT HIGH ENERGY PIPE
BREAKS, REACTOR WATER
CLEANUP, OUTSIDE CONTAINMENT Amendment, 24 3-xl February 1986

Nine Mile Point Unit 2 FSAR Figure Number 3.6A-39 CHAPTER 3 IIST OF FIGURES (Cont)

Title HIGH ENERGY PIPE

BREAKS, REACTOR WATER
CjEANUP, OUTSIDE CONTAINMENT Amendment 12 3-xla J

June 1984

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONAjIYBI'ANK Amendment 12 3-xlb

Nine Mile Point Unit 2 FSAR Y

CHAPTER 3 LIST OF FIGURES (Cont'd)

Figure Number

3. 6A-40 Title HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT
3. 6A-41 3.6A-42 HIGH ENERGY PIPE BREAKS REACTOR WATER CLEANUP OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS STANDBY LIQUID CONTROL INSIDE CONTAINMENT 3.6A-43
3. 6A-44
3. 6A-45
3. 6A-46
3. 6A-47
3. 6A-48 3,6A-49 3.6A-50 3.6A-51 3.6A-52 HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSiDE CONTAINMENT HIGH ENERGY PIPE BREAKS CONTROL ROD DRIVE SYSTEM OUTSIDE CONTAINMENT DELETED DELETED HIGH ENERGY PIPING COMPOSITE PLAN FL 175I Pn AND 215I 0
3. 6A-53 HIGH ENERGY PIPING COMPOS1TE PLAN EL 240'-0"
3. 6A-54 HIGH ENERGY PIPING COMPOSITE PLAN EL 261'-0" USAR Revision 2

3-xli October 1990

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont'd)

Figure Number Title

3. 6A-55 HIGH ENERGY PIPING COMPOSITE PLAN EL 289'-0"

[

3.6A-56 HIGH ENERGY PIPING COMPOSITE PLAN EL 306'-6" 3.6A-57 HIGH ENERGY PIPING COMPOSITE PLAN EL 328'-10" I

3.6A-58 I

3.6A-59 3 'A-60 3.6B-1 3.6B-2 3.6B-3 3.7A-1 3.7A-2 HIGH ENERGY PIPING COMPOSITE SECTION 1-1 HIGH ENERGY PIPING COMPOSITE SECTION 2-2 HIGH ENERGY PIPING COMPOSITE SECTIONS 3-3 AND 4-4 TYPICAL RESTRAINT FORCE DEFLECTION CURVE TYPICAL PIPE WHIP RESTRAINT CONFlGURATION BREAK LOCATIONS AND RESTRAINTS ANALYZED~

PDA VERIFICATION PROGRAM HORIZONTAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G

VERTICAL SSE DESIGN RESPONSE SPECTRA NORMALIZED TO 0.15 G

3.7A-3 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTH-QUAKE) BASED ON 2.0 PERCENT DAMPING RATIO 3.7A-4 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM. DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 1 PERCENT DAMPING RATIO USAR Revision 2

3-xlil October 1990

Nine Mile Point Unit 2 FSAR Le THIS PAGE INTENTIONAjjYBjANK

~

~

Amendment 21 3-xli2 September 198S

iNine Mi'le'. Point Unit 2 'FSAR Figure Number 3.7A-S 3.7A-6 CHAPTER 3

LIST OF FIGURES (Cont)

Title HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 5.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 7.0 PERCENT DAMPING RATIO 3.7A-7 3.7A-8 3.7A-9 3.7A-10 3.7A-11 3.7A-12 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 10.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND ~ RESPONSE SPECTRUM DERIVED FROM HORI" ZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTHQUAKE) BASED ON 1.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTHQUAKE)

BASED ON 2.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 5.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 7.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 10.0 PERCENT DAMPING RATIO

Nine Mile Point Unit 2 FSAR THIS PAGE INTENTIONALLYBLANK Amendment 12 3-xlib June 1984

Nine'Mile Point Unit'2 FSAR Figure Number CHAPTER 3 LIST OF FIGURES (Cont)

Title 3.7A-5 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 5.0 PERCENT DAMPING RATIO 3.7A-6 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 7.0 PERCENT DAMPING RATIO 3.7A-7 HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (EAST-WEST EARTHQUAKE)

BASED ON 10.0 PERCENT DAMPING RATIO 3.7A-S 3.7A-9 3.7A-10 3.7A-11 3.7A-12 HORIZONTAL SSE:DESIGN

.RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORI-ZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTHQUAKE) BASED ON 1.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTHQUAKE)

BASED ON 2.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND RESPONSE SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 5.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 7.0 PERCENT DAMPING RATIO HORIZONTAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM HORIZONTAL SSE SYNTHETIC TIME HISTORY (NORTH-SOUTH EARTH-QUAKE) BASED ON 10.0 PERCENT DAMPING RATIO

Nine Mile Point Unit 2 FSAR Figure Number 3.7A-13 CHAPTER 3 LIST OF FIGURES (Cont)

Title VERTICAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM VERTICAL SSE SYNTHETIC TIME HISTORY BASED ON 1.0 PERCENT DAMPING RATIO 3.7A-14 3.7A-15 3.7A-16 3.7A-17 3.7A-18 3.7A-19 3.7A-20 3.7A-21 VERTICAL SSE DESIGN.RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM VERTICAL SSE SYNTHETIC TIME HISTORY BASED ON 2.0 PERCENT DAMPING RATIO VERTICAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM VERTICAL SSE SYNTHETIC TIME HISTORY BASED ON 5.0 PERCENT DAMPING RATIO VERTICAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM VERTICAL SSE SYNTHETIC TIME HISTORY BASED ON 7.0 PERCENT DAMPING RATIO VERTICAL SSE DESIGN RESPONSE SPECTRUM AND

RESPONSE

SPECTRUM DERIVED FROM VERTICAL SSE SYNTHETIC TIME HISTORY BASED ON 10.0 PERCENT DAMPING RATIO DYNAMIC MODEL FOR SEISMIC ANALYSIS OF PRIMARY CONTAINMENT DYNAMIC MODEL FOR SEISMIC ANALYSIS OF REACTOR BUILDING WALL DYNAMIC MODEL FOR SEISMIC ANALYSIS OF THE CONTROL AND DIESEL GENERATOR BUILDINGS SSE PRIMARY CONTAINMENT CRACKED CONDITION ACCELERATION PROFIIE (G)

EAST-WEST DIRECTION 24 3.7A-22 SSE PRIMARY CONTAINMENT CRACKED CONDITION ACCELERATION PROFILE (GS)

VERTICAL DIRECTION Amendment 24 3-xliii February 1986

Nine Mile Point Unit 2

FSAR Figure Number CHAPTER 3

LIST OF FIGURES (Cont)

Title 3.7A-23 SSE PRIMARY ACCELERATION DIRECTION CONTAINMENT CRACKED CONDITION PROFILE'GS)

NORTH-SOUTH 3.7A-24 3.7A-25 SSE PRIMARY ACCELERATION DIRECTION SSE PRIMARY ACCELERATION CONTAINMENT UNCRACKED CONDITION PROFILE (GS)

EAST-WEST CONTAINMENT UNCRACKED CONDITION PROFILE (GS)

'VERTICAL DIRECTION 3.7A-26 3.7A-27 3.7A-28 3.7A-29 3.7A-30 3.7A-31 3.7A-32 3.7A-33 SSE PRIMARY CONTAINMENT UNCRACKED CONDITION ACCELERATION PROFILE (GS)

NORTH-SOUTH DIRECTION SSE REACTOR BUILDING WALL ACCELERATION PROFILE (GS)

EAST-WEST DIRECTION SSE REACTOR BUILDING WALL ACCELERATION PROFILE (GS)

VERTICAL DIRECTION SSE REACTOR BUILDING WALL ACCELERATION PROFILE (GS)

NORTH-SOUTH DIRECTION SSE CONTROL AND DIESEL GENERATOR BUILDINGS ACCELERATION PROFILE (GS)

EAST-WEST DIRECTION SSE CONTROL AND DIESEL GENERATOR BUILDINGS ACCELERATION PROFILE (GS)

VERTICAL DIRECTION SSE CONTROL AND DIESEL'ENERATOR BUILDINGS ACCELERATION PROFILE (GS)

NORTH-SOUTH DIRECTION PLAN AND SECTIONS FOR DUCTLINES 907 g 922 g ELECTRICAL MANHOLE NO. li AND DIESEL GENERATOR BUILDING FLOOR SLABS 3.7A-'34 ALTERNATIVE DAMPING VALUES PER ASME CODE CASE N-411 3.7A-35 3.7A-36 RELATIVE DISPLACEMENT BETWEEN REACTOR BUILDING AND PRIMARY CONTAINMENT JUSTIFICATION OF STATIC COEFFICIENT OF 13 (SHEETS 1 AND 2)

USAR Revision 3-xliv April 1989

Nine Mile Point Unit 2 FSAR Figure Number 3.7B-l 3.7B-2 3.7B-3 3.8-1 CHAPTER 3

LIST OF FIGURES (Cont)

Title SEISMIC ANALYTICAL MODEL FOR NSSS COMPONENTS REACTOR PRESSURE VESSEL AND INTERNALS SEISMIC'ODEL DENSITY OF STRESS REVERSALS PRIMARY CONTAINMENT'INER ELEVATION@

AND DETAILS USAR Revision 0

3-xliva April 1989

Nine Mile Point Uni'tSAR c

NALLY BLANK Amendment 18 3-xlivb March 1985

Nine Mile Point Unit 2 FSAR Figure Number CHAPTER 3 LIST OF FXGURES (Cont'd)

Title 3.8-2 3.8-3 3.8-3a 3.8-4 3.8-5 3.8-6 PRIMARY CONTAINMENT'INER FLOOR PRIMARY CONTAINMENT WALLi SECTION VIEW PRIMARY CONTAINMENT WALL REINFORCING DETAILS EL 175'-0" TO 241'-1",

AZIMUTH 180 TO 360 PRIMARY CONTAINMENT WALL, STRUCTURAL DETAILS AROUND DRYWELL ACCESS HATCHES PRIMARY CONTAINMENT~ TYPICAL BEAM SEAT DETAILS COMBINATION EQUIPMENT HATCH AND PERSONAL AIRLOCK AND ESCAPE AIRLOCK PRIMARY CONTAINMENT 3.8-7 3.8-8 3.8-9 CONTROL ROD DRXVE REMOVAL HATCH AND SUPPRESSION POOL ACCESS HATCH DRYWELL HEAD AND FINGER PIN CLOSURE DETAILS OTHER PIPING AND INSTRUMENT PENETRATXONS THROUGH PRIMARY CONTAINMENT 3.8-10 THERMALLY HOT AND THERMALLY COLD PIPXNG PENETRATIONS THROUGH PRIMARY CONTAINMENT 3.8-11 3.8-12 3.8-13 3.8-14 3.8-15 3.8-16 3.8-17 PRIMARY CONTAINMENT AND INTERNAL STRUCTURES AREVQTGEMENT OF PENETRATIONS THROUGH DRYWELL FLOOR TYPXCAL REINFORCXNG BAR DETAXLS FOR DRYWELL FLOOR TYPXCAL REINFORCING BAR DETAILS FOR RPV PEDESTAL BXOLOGICAI SHIELD WALL DETAXLS RING GIRDER~

STAR TRUSS, AND STABILIZER ARRANGEMENT TYPICAL DETAILS AT CONSTRUCTION JOINTS AND SPACES BETWEEN BUILDING AND ROCK SURFACE 3.8-18 EXTERIOR REACTOR BUILDING WALL TYPICAL REINFORCING ARRANGEMENT (SHEETS 1 AND 2)

USAR Revision 4

3-x1v October 1992

Nine Nile Point Unit 2 FSAR Figure Number CHAPTER 3'IST OF FIGURES (Cont'd)

Title 3.8-19 3.8-20 h

3.8-21 3.8-22 3.8-23 3.9A-1 SPENT FUEL POOL GIRDERS PLANT AND ELEVATION (SHEETS 1 AND 2)

REINFORCEMENT REACTOR BUILDING MAT TYPICAL DETAIL WALL/COLUMN TO FOUNDATION MAT JUNCTION CONTAINMENT MAT TOP REINFORCING DETAILS CONTAINMENT MAT BOTTOM REINFORCING DETAILS TYPICAL SAFETY CLASSES 2 AND 3 TUBE SUPPORTS AND MARKING 3.9A-2 3.9A-3 3.9A-4 3.9A-5 3.9A-6 3.9A-7 3.9A-8 3.9A-9 3.9A-10 3.9A-11 3.9A-12 3.9A-13 3.9A-14 3.9A-15 ARS OF ACC.

ARS OF ACC.

ARS OF ACC.

ARS OF ACC.

SHIELD WALL (ELEV 315.08 FT)

RPV SHELL (ELEV 332.70 FT)

RPV SHELL (ELEV 332.70 FT)

PRIMARY CONT.

(ELEV 196.67 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 196.67 FT)

ARS OF ACC.

ARS OF ACC.

SHIELD WALL (ELEV 315.08 FT)

SHIELD WALL (ELEV 315.08 FT)

T'YPICAL PLATE AND SHELL TYPE SUPPORT JURISDICTIONAL BOUNDARIES TYPICAL PLATE AND SHELL TYPE SUPPORT JURISDICTIONAL BOUNDARIES TYPICAL LINEAR TYPE SUPPORT JURISDICTIONAL BOUNDARIES PIPE SUPPORT JURISDICTIONAL BOUNDARIES ARS OF ACC. PRIMARY CONT.

(ELEV 196.67 FT)

ARS OF ACC. PRIMARY CONT.

(ELEV 196.67 FT)

ARS OF ACC.

SHIELD WALL (ELEV 315.08 FT)

USAR Revision 4

3-xlvi October 1992

Nine Mile Point Unit 2

FSAR Figure Number 3.9A-16 3.9A-17 3.9A-18 3.9A-19 3.9A-20 3.9A-21 3.9A-22 3.9A-23 3.9A-24 3.9A-25 3.9A-26 3.9A-27 3 'A-28 3.9A-29 3.9A-30 3.9A-31 3.9A-32 3.9A-33 3.9A-34 3.9A-35 3.9A-36 3.9A-37 3.9A-38 CHAPTER 3

LIST OF FIGURES (Cont)

Title ARS OF ACC.

RPV SHELL (ELEV 332.70 FT)

ARS OF ACC.

RPV SHELL (ELEV 332.70 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)'RS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF= ACC.

RPV SHELL (ELEV 315.08 FT)

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS.OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS. OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

'RS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS.OF

'ACC. 'SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

USAR Revision 0

3-xlvii April 1989

Nine Mile Point Unit 2

FSAR Figure Number 3.9A-39 3.9A-40 3.9A-41 3.9A-42 3.9A-43 3.9A-44 3.9A-45 3.9A-46 3.9A-47 3.9A-48 3.9A-49 3.9A-50 3.9A-51 3.9A-52 3.9A-53 3.9A-54 3;9A-55 3.9A-56 3.9A-57 3.9A-58 3.9A-59 3.9A-60 3.9A-61 CHAPTER 3

LIST OF FIGURES (Cont)

ARS ARS OF ACCELERATION OF ACCELERATION OF ACCELERATION OF ACCELERATION PRIMARY CONT. EL. 196.67 FT PRIMARY CONT. EL. 196.67 FT PRIMARY CONT.

EL. 196.67 FT PRIMARY CONT. EL. 196.67 FT ARS OF ACCELERATION PRIMARY CONT. EL. 196.67 FT ARS OF ACCELERATION PRIMARY CONT. EL. 196.67 FT ARS OF ACCELERATION SHIELD WALL EL.

315.09 FT

'RS OF ACCELERATION SHIELD WALL EL. 315.09 FT ARS OF ACCELERATION SHIELD WALL EL. 315.09 FT ARS OF ACCELERATION SHIELD WALL EL. 315.09 FT ARS OF ACCELERATION SHIELD,WALL EL.

315.09 FT ARS OF ACCELERATION SHIELD WALL EL. 315.09 FT Title

\\

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

SECONDARY CONT.

(ELEV 175)

AT MAT ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 206.11 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF ACC.

SHIELD WALL OUT (ELEV 315.23 FT)

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS OF ACC.

RPV SHELL (ELEV 315.08 FT)

ARS OF ACC.

PRIMARY CONT.

(ELEV 176.0 FT)

AT MAT ARS OF ACC.

PRIMARY CONT.

(ELEV 176.0 FT)

AT MAT USAR Revision 0

3-xlviii April 1989

Nine Mile Point Unit 2 FSAR CHAPTER 3 LIST OF FIGURES (Cont'd.)

Figure Number Title 3.9A-62 3.9A-63 3.9A-64 3.9A-65 3.9A-66 3.9A-67 3.9B-1 3.9B-2 3.9B-3 3.9B-4 3.9B-5 3.10B-1 3.10B-2 3.10B-3 3.10B-4 ARS OF ACCELERATION RPV SHELL EL. 332.70 FT ARS OF ACCELERATION RPV SHELL EL. 332.70 FT ARS OF ACCELERATION RPV SHELL EL. 332.70 FT ARS OF ACCELERATION RPV SHELL EL. 332.70 FT ARS OF ACCELERATION RPV SHELL EL. 332.70 FT ARS OF ACCELERATION RPV SHELL EL.

DELETED REACTOR INTERNALS FLON PATHS 332.70 FT FLUE SUPPORT PIECES JET PUMP DELETED DELETED PRESSURE NODES USED FOR DEPRESSURZZATZON ANALYSIS DELETED DELETED USAR Revision 4

3-xlix October 1992

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